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1
Content available remote Treatment of Wastewater to Meet the Requirements for Cooling Water Systems in Jordan’s Nuclear Plants
100%
Al-Rawajfeh A. E. , Araj K.
Chemical and Process Engineering
|
2013
|
tom 34
|
nr 2
253-267
EN
Scaling and corrosion associated with the use of natural hard water in cooling towers during recirculation pose great problems from both economical and technical points of view, such as decreased system efficiency and increased frequency of chemical cleaning. Treated municipal wastewater (MWW) is a promising alternative to freshwater as power plant cooling system makeup water, especially in arid regions. In this work, hybrid systems of salt precipitation (SP), nanofiltration (NF) and reverse osmosis (RO) were investigated, as potential pretreatment processes for wastewater reuse as cooling water in the planned Jordan nuclear power plants. The As-Samra wastewater was used to calculate the potential of carbonate and sulfate scale formation. The results were compared to scale potentials from Palo Verde wastewater. Four cases were investigated; SP, NF, SP-RO and NF-RO. The SP pretreatment cases showed the highest monovalent to divalent ratio because of a high removal of Ca and Mg and addition of Na from the chemicals of the SP step. The NF pretreatment cases, showed the lowest calcium sulfate scale potential and this potential decreases with the % pretreatment. The scale amount increases very slightly with concentration times when the SP and NF product is desalinated by RO step.
2
Content available Treatment of Wastewater to Meet the Requirements for Cooling Water Systems in Jordan’s Nuclear Plants
88%
Al-Rawajfeh A. E. , Araj K.
|
2013
|
nr 2
3
Content available Stress Corrosion Cracking Properties of Steam Generator Tubing Alloys in Crevice Environment
88%
Shin J.-H. , Kim D.-J.
Archives of Metallurgy and Materials
|
2019
|
tom Vol. 64, iss. 2
543--545
EN
The safe and reliable operation of pressurized water reactors (PWRs) depends on the integrity of structural material. In particular, the failure of steam generator (SG) tubes on the secondary side is one of the major concerns of operating nuclear power plants. To establish remediation techniques and manage damage, it is necessary to articulate the mechanism through which various impurities affect the SG tubes. This research aims to understand the effect of impurities (e. g., S, Pb, and Cl) on the stress corrosion cracking of Alloy 600 and 690.
4
Content available Treatment of wastewater to meet the requirements for cooling water systems in jordan’s nuclear plants
75%
Al-Rawajfeh A. E. , Araj K.
Chemical and Process Engineering
|
2013
|
tom Vol. 34, nr 2
253--267
EN
Scaling and corrosion associated with the use of natural hard water in cooling towers during recirculation pose great problems from both economical and technical points of view, such as decreased system efficiency and increased frequency of chemical cleaning. Treated municipal wastewater (MWW) is a promising alternative to freshwater as power plant cooling system makeup water, especially in arid regions. In this work, hybrid systems of salt precipitation (SP), nanofiltration (NF) and reverse osmosis (RO) were investigated, as potential pretreatment processes for wastewater reuse as cooling water in the planned Jordan nuclear power plants. The As-Samra wastewater was used to calculate the potential of carbonate and sulfate scale formation. The results were compared to scale potentials from Palo Verde wastewater. Four cases were investigated; SP, NF, SP-RO and NF-RO. The SP pretreatment cases showed the highest monovalent to divalent ratio because of a high removal of Ca and Mg and addition of Na from the chemicals of the SP step. The NF pretreatment cases, showed the lowest calcium sulfate scale potential and this potential decreases with the % pretreatment. The scale amount increases very slightly with concentration times when the SP and NF product is desalinated by RO step.
5
Content available Stress Corrosion Cracking Properties of Steam Generator Tubing Alloys in Crevice Environment
75%
Shin J.-H. , Kim D.-J.
|
|
nr 2
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